EP3453026B1 - Nuclear reactor with fuel elements equipped with a cooling duct - Google Patents
Nuclear reactor with fuel elements equipped with a cooling duct Download PDFInfo
- Publication number
- EP3453026B1 EP3453026B1 EP17733004.0A EP17733004A EP3453026B1 EP 3453026 B1 EP3453026 B1 EP 3453026B1 EP 17733004 A EP17733004 A EP 17733004A EP 3453026 B1 EP3453026 B1 EP 3453026B1
- Authority
- EP
- European Patent Office
- Prior art keywords
- fuel
- fuel elements
- active part
- nuclear reactor
- tubular structure
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
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Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/322—Means to influence the coolant flow through or around the bundles
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Definitions
- the present invention relates to a nuclear reactor, in particular a nuclear reactor cooled with liquid metal or molten salts, constituted by a number of fuel elements characterized by a cooling system during fuel replacement of new conception.
- the active part of the fuel elements is completely immersed in the cooling fluid, with possibly only the inactive head emerging above the hot manifold level.
- the exhausted elements are transferred from the liquid metal or molten salts of the reactor to an auxiliary water pool.
- the operation requires extraction of the exhausted fuel elements from the reactor and their cooling via forced gas circulation during the entire transfer period to the water pool, this circulation being implemented by coupling the fuel element to an auxiliary circuit of the fuel transfer machine via the grippers of said fuel transfer machine, which connect to the head of the fuel element.
- a cooling duct runs from the head of the fuel element and reaches the fuel rods contained in a box-like structure that, as a rule, extends beyond the lower active end of the fuel element and is in hydraulic continuity with the foot of the fuel element, in turn provided with a duct through which primary cooling fluid enters during normal reactor operation, and auxiliary cooling gas exits in the fuel replacement situation.
- Cooling must always be ensured, also taking into account possible unforeseen circumstances, such as the temporary blockage of the fuel element in any position along the transfer path.
- Exemplary prior art documents are US 4 675 154 A , US 3 406 090 A , or GB 845 804 A .
- One object of the present invention is to provide a nuclear reactor that overcomes the indicated drawbacks of known solutions and has further constructional and safety advantages.
- the present invention thus relates to a nuclear reactor, as defined in the appended claim 1 and, for its auxiliary characteristics and plant configurations, in the dependent claims.
- the nuclear reactor 1 comprises a substantially cup or pool-shaped vessel 2 and a closure structure 3 placed on top of the vessel 2; the vessel 2 contains a core 4 and a hydraulic separation structure 5 delimiting a hot manifold 6 and a cold manifold 7 in which a primary cooling fluid F of the core 4 circulates.
- the primary fluid F has a free surface that in normal operation of the reactor 1 is at different levels H1 and H2 in the manifolds 6 and 7.
- the vessel 2 houses circulating pumps 8 for the primary fluid F, heat exchangers 9 through which the primary fluid F passes and which transfer the power generated in the core 4 to a secondary fluid, as well as other known components that are not shown.
- An anchoring structure 11 for the fuel elements 12 is inserted inside the upper part 10 of the hydraulic separation structure 5.
- the fuel elements 12 extend along respective longitudinal and parallel axes (A) and have respective active parts 13 and respective service parts 14, which comprise a foot 15 and a head 16, respectively at the bottom and the top of the fuel elements, and a connection shaft 17 between the active part 13 and the head 16.
- the shaft 17 possesses a certain amount of mechanical flexibility and is inserted with its upper portion 18 in an empty cylindrical volume inside the head 16 of the fuel element 12.
- This upper portion 18 is mechanically coupled to the head 16 by a spherical coupling 19, not described in detail as it is current technology, located at its top end.
- the feet 15 of the fuel elements 12 are in contact with each other and, as a whole, constitute a bundle that is radially constrained by the inner rim 20 of the opening 21 on the bottom of the hydraulic separation structure 5.
- the head 16 of the fuel element 12 houses support devices 22 that constrain the fuel elements 12 to one another and to the anchoring structure 11.
- the heads 16 of the fuel elements 12 are above the level H1 of the primary fluid in the hot manifold, while the respective active parts 13 are completely immersed to enable their cooling via circulation of primary cooling fluid, which enters from the cold manifold 7 to the fuel elements 12 through respective feet 15, and exits into the hot manifold 6 through the upper support grid 23 of the fuel rods 24 that is provided with holes 25.
- the shaft 17 is hollow and hydraulically connected to a tubular structure 26 that extends centrally for the entire active part 13 of the fuel elements 12.
- the tubular structure 26 is characterized by being provided with a plurality of small holes 27 along the entire length corresponding to the active part 13 of the fuel element 12.
- the tubular structure 26 is conveniently closed at the bottom end by a threaded coupling with a plug 29 that, together with a shoulder 30 made on the tubular structure 26, constitutes the locking system of the lower grid 31 of the fuel element 12.
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
- The present invention relates to a nuclear reactor, in particular a nuclear reactor cooled with liquid metal or molten salts, constituted by a number of fuel elements characterized by a cooling system during fuel replacement of new conception.
- During normal operation of the reactor, the active part of the fuel elements is completely immersed in the cooling fluid, with possibly only the inactive head emerging above the hot manifold level.
- During fuel replacement, the exhausted elements are transferred from the liquid metal or molten salts of the reactor to an auxiliary water pool. The operation requires extraction of the exhausted fuel elements from the reactor and their cooling via forced gas circulation during the entire transfer period to the water pool, this circulation being implemented by coupling the fuel element to an auxiliary circuit of the fuel transfer machine via the grippers of said fuel transfer machine, which connect to the head of the fuel element. A cooling duct runs from the head of the fuel element and reaches the fuel rods contained in a box-like structure that, as a rule, extends beyond the lower active end of the fuel element and is in hydraulic continuity with the foot of the fuel element, in turn provided with a duct through which primary cooling fluid enters during normal reactor operation, and auxiliary cooling gas exits in the fuel replacement situation.
- Cooling must always be ensured, also taking into account possible unforeseen circumstances, such as the temporary blockage of the fuel element in any position along the transfer path.
- Obviously, the most critical situation is of possible blockage with the active part of the fuel element partially or totally extracted from the primary cooling fluid, with the foot of the element still immersed in the primary cooling fluid and the circulation of auxiliary cooling gas prevented by blockage of the circulation duct with the primary cooling fluid in which it is still partially immersed.
-
- One object of the present invention is to provide a nuclear reactor that overcomes the indicated drawbacks of known solutions and has further constructional and safety advantages.
- The present invention thus relates to a nuclear reactor, as defined in the appended
claim 1 and, for its auxiliary characteristics and plant configurations, in the dependent claims. - The invention is described in the following non-limitative embodiment, referring to the figures of the accompanying drawings, in which:
-
Figure 1 is a schematic overall view in longitudinal section of a nuclear reactor according to the invention; and -
Figure 2 is an enlarged view in longitudinal section of the active part of the core of the reactor inFigure 1 . - Referring to
Figure 1 , particularly representative of a liquid-metal or molten salt coolednuclear reactor 1, thenuclear reactor 1 comprises a substantially cup or pool-shaped vessel 2 and aclosure structure 3 placed on top of thevessel 2; thevessel 2 contains a core 4 and ahydraulic separation structure 5 delimiting ahot manifold 6 and acold manifold 7 in which a primary cooling fluid F of the core 4 circulates. The primary fluid F has a free surface that in normal operation of thereactor 1 is at different levels H1 and H2 in themanifolds vessel 2 houses circulatingpumps 8 for the primary fluid F,heat exchangers 9 through which the primary fluid F passes and which transfer the power generated in the core 4 to a secondary fluid, as well as other known components that are not shown. - An
anchoring structure 11 for thefuel elements 12 is inserted inside theupper part 10 of thehydraulic separation structure 5. - Referring to
Figure 2 as well, thefuel elements 12 extend along respective longitudinal and parallel axes (A) and have respectiveactive parts 13 andrespective service parts 14, which comprise afoot 15 and ahead 16, respectively at the bottom and the top of the fuel elements, and aconnection shaft 17 between theactive part 13 and thehead 16. - The
shaft 17 possesses a certain amount of mechanical flexibility and is inserted with itsupper portion 18 in an empty cylindrical volume inside thehead 16 of thefuel element 12. Thisupper portion 18 is mechanically coupled to thehead 16 by aspherical coupling 19, not described in detail as it is current technology, located at its top end. - The
feet 15 of thefuel elements 12 are in contact with each other and, as a whole, constitute a bundle that is radially constrained by theinner rim 20 of theopening 21 on the bottom of thehydraulic separation structure 5. - The
head 16 of thefuel element 12 housessupport devices 22 that constrain thefuel elements 12 to one another and to theanchoring structure 11. - Under normal reactor operating conditions, the
heads 16 of thefuel elements 12 are above the level H1 of the primary fluid in the hot manifold, while the respectiveactive parts 13 are completely immersed to enable their cooling via circulation of primary cooling fluid, which enters from thecold manifold 7 to thefuel elements 12 throughrespective feet 15, and exits into thehot manifold 6 through theupper support grid 23 of thefuel rods 24 that is provided withholes 25. - The
shaft 17 is hollow and hydraulically connected to atubular structure 26 that extends centrally for the entireactive part 13 of thefuel elements 12. - The
tubular structure 26 is characterized by being provided with a plurality ofsmall holes 27 along the entire length corresponding to theactive part 13 of thefuel element 12. Thetubular structure 26 is conveniently closed at the bottom end by a threaded coupling with aplug 29 that, together with ashoulder 30 made on thetubular structure 26, constitutes the locking system of thelower grid 31 of thefuel element 12. - With a hydraulically sealed coupling between the grippers of the fuel replacement machine, both known solutions and not described within present invention, and the
head 16 of thefuel element 12, and by means of the hydraulic duct that runs from thehead 16 and through theshaft 17 to feed thetubular structure 26 of the fuel element, it is possible to inject cooling gas through theholes 27 of thetubular structure 26 and inside theactive part 13 of thefuel elements 12 during fuel replacement operations. - A similar possibility also exists with different constructional solutions for the
fuel element 12, such as those that do not provide for ashaft 17, but a head connected directly to theupper grid 23. - The advantages of the present invention clearly emerge from the foregoing description:
- the availability of a system of injecting cooling gas along the entire axial profile of the
active part 13 of thefuel element 12 allows cooling the active part of the element even in a hypothetical, accidental situation during the replacement operation, where thefuel element 12 remains blocked in a position where only theactive part 13 of theelement 12, or only a portion thereof, emerges above the level H1 of the primary cooling fluid and the circulation of cooling gas through the entireactive part 13 is obstructed by the primary cooling fluid that prevents discharge of cooling gas through thefoot 15; in this case, the part that protrudes from the primary cooling fluid is cooled by gas escaping from thesmall holes 27 in correspondence to the emergedactive parts 13 and which leaves thefuel element 12 through theholes 25 in theupper grid 23. - the injection of cooling gas from inside the
active parts 13 particularly favours cooling the inner fuel rods that, unlike the outer ones, cannot be efficiently cooled by outward irradiation from theactive parts 13. - the
tubular structure 26, which extends for the entireactive part 13 of thefuel elements 12, can be conveniently used as a support for the lower grid and, if necessary, also as a support for intermediate grids of the fuel rods. - the
tubular structure 26, which extends for the entireactive part 13 of thefuel elements 12, can be conveniently used to house control rods of the core 4, rods that are to be removed before extraction of thefuel element 12 to use thetubular structure 26 as a hydraulic duct for cooling gas injection. - Finally, it is understood that numerous modifications and variants can be made regarding the reactor set forth herein without departing from the scope of the appended claims.
Claims (4)
- A nuclear reactor (1), comprising a vessel (2) that houses a core (4), comprising a bundle of fuel elements (12) being arranged to be immersed in a primary cooling fluid, F, of the core; the reactor being characterized in that the fuel elements (12) comprise a head (16), fuel rods (24) forming an active part (13), and a connection shaft (17) between the active part (13) and the head (16), wherein the fuel elements (12) extend along respective longitudinal and parallel axes, A, and wherein the head (16) of said fuel elements (12) is by means of the connection shaft (17) hydraulically connected to a tubular structure (26) that extends centrally for the entire active part (13) of the fuel elements (12); the tubular structure (26) being hydraulically sealed at the bottom end (28) and provided with a plurality of holes (27) along the entire length corresponding to the active part (13) of the fuel elements (12).
- The nuclear reactor according to claim 1, wherein the tubular structure (26) is closed at a bottom end (28) by a plug (29) that, together with a shoulder (30) made on the tubular structure (26), constitute a locking system of a lower grid (31) of the fuel elements (12).
- The nuclear reactor according to claim 1, wherein, by means of a hydraulically sealed coupling between grippers of a fuel replacement machine and the head (16) of the fuel elements (12), it is possible to inject cooling gas through the holes (27) of the tubular structure (26) and inside the active part (13) of the fuel elements (12) during fuel replacement operations.
- The nuclear reactor according to claim 1, wherein, during fuel replacement operations, it is possible to make the cooling gas escape from the fuel elements (12) through holes (25) in an upper support grid (23) of the fuel rods (24).
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
ITUA2016A003715A ITUA20163715A1 (en) | 2016-05-04 | 2016-05-04 | NUCLEAR REACTOR WITH FUEL ELEMENTS PROVIDED WITH COOLING DUCT |
PCT/IB2017/052607 WO2017191594A1 (en) | 2016-05-04 | 2017-05-04 | Nuclear reactor with fuel elements equipped with a cooling duct |
Publications (2)
Publication Number | Publication Date |
---|---|
EP3453026A1 EP3453026A1 (en) | 2019-03-13 |
EP3453026B1 true EP3453026B1 (en) | 2020-03-25 |
Family
ID=56853769
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP17733004.0A Active EP3453026B1 (en) | 2016-05-04 | 2017-05-04 | Nuclear reactor with fuel elements equipped with a cooling duct |
Country Status (6)
Country | Link |
---|---|
EP (1) | EP3453026B1 (en) |
JP (1) | JP6875419B2 (en) |
KR (1) | KR102395713B1 (en) |
CN (1) | CN109478429A (en) |
IT (1) | ITUA20163715A1 (en) |
WO (1) | WO2017191594A1 (en) |
Family Cites Families (15)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CH348476A (en) * | 1957-05-31 | 1960-08-31 | Escher Wyss Ag | Fissile material element |
GB1086060A (en) * | 1963-12-02 | 1967-10-04 | Atomic Energy Authority Uk | Improvements in or relating to nuclear reactors |
GB1093618A (en) * | 1964-12-08 | 1967-12-06 | Atomic Energy Authority Uk | Improvements in or relating to nuclear reactors |
GB1545813A (en) * | 1975-06-02 | 1979-05-16 | Commissariat Energie Atomique | Control rod assembly for nuclear reactor |
GB1550978A (en) * | 1977-06-24 | 1979-08-22 | Shumyakin E P | And others methods and apparatus for refuelling nuclear reactors |
JPS59150381A (en) * | 1983-02-14 | 1984-08-28 | 株式会社東芝 | Fast breeder |
JPS59176692A (en) * | 1983-03-28 | 1984-10-06 | 株式会社東芝 | Fast breeder reactor |
US4675154A (en) * | 1985-12-20 | 1987-06-23 | General Electric Company | Nuclear fuel assembly with large coolant conducting tube |
JPH08220276A (en) * | 1995-02-15 | 1996-08-30 | Hitachi Ltd | Core upper structure for nuclear reactor |
JPH11133172A (en) * | 1997-10-24 | 1999-05-21 | Mitsubishi Heavy Ind Ltd | Internal structure of fast breeding reactor |
JP2000075083A (en) * | 1998-08-31 | 2000-03-14 | Hitachi Ltd | Fast reactor and mist separator used for the fast reactor |
FR2864326B1 (en) * | 2003-12-22 | 2006-02-24 | Framatome Anp | METHOD FOR LIMITING HOLDING EFFORTS EXERCISED ON FUEL ASSEMBLY OF A NUCLEAR REACTOR AND FUEL ASSEMBLY |
WO2009040644A2 (en) * | 2007-09-26 | 2009-04-02 | Del Nova Vis S.R.L. | Nuclear reactor, in particular pool-type nuclear reactor, having new concept fuel elements |
US7995701B2 (en) * | 2008-05-21 | 2011-08-09 | Westinghouse Electric Company Llc | Nuclear core component hold-down assembly |
CA2876524A1 (en) * | 2012-06-13 | 2013-12-19 | Atomic Energy Of Canada Limited/Energie Atomique Du Canada Limitee | A pressure-tube nuclear reactor with a low pressure moderator and fuel channel assembly |
-
2016
- 2016-05-04 IT ITUA2016A003715A patent/ITUA20163715A1/en unknown
-
2017
- 2017-05-04 CN CN201780027642.2A patent/CN109478429A/en active Pending
- 2017-05-04 JP JP2018557827A patent/JP6875419B2/en active Active
- 2017-05-04 KR KR1020187033402A patent/KR102395713B1/en active IP Right Grant
- 2017-05-04 EP EP17733004.0A patent/EP3453026B1/en active Active
- 2017-05-04 WO PCT/IB2017/052607 patent/WO2017191594A1/en unknown
Non-Patent Citations (1)
Title |
---|
None * |
Also Published As
Publication number | Publication date |
---|---|
JP6875419B2 (en) | 2021-05-26 |
ITUA20163715A1 (en) | 2017-11-04 |
CN109478429A (en) | 2019-03-15 |
EP3453026A1 (en) | 2019-03-13 |
JP2019515295A (en) | 2019-06-06 |
WO2017191594A1 (en) | 2017-11-09 |
KR20190002534A (en) | 2019-01-08 |
KR102395713B1 (en) | 2022-05-09 |
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